کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
7964306 1514171 2016 12 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Development of radiation damage during in-situ Kr++ irradiation of FeNiCr model austenitic steels
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
پیش نمایش صفحه اول مقاله
Development of radiation damage during in-situ Kr++ irradiation of FeNiCr model austenitic steels
چکیده انگلیسی
In situ irradiations of 15Cr/15NiTi and 15Cr/25NiTi model austenitic steels were performed at the Intermediate Voltage Electron Microscope (IVEM)-Tandem user Facility (Argonne National Laboratory) at 600 °C using 1 MeV Kr++. The experiment was designed in the framework of cladding development for the GEN IV Sodium Fast Reactors (SFR). It is an extension of previous high dose irradiations on those model alloys at JANNuS-Saclay facility in France, aimed at investigating swelling mechanisms and microstructure evolution of these alloys under irradiation [1]. These studies showed a strong influence of Ni in decreasing swelling. In situ irradiations were used to continuously follow the microstructure evolution during irradiation using both diffraction contrast imaging and recording of diffraction patterns. Defect analysis, including defect size, density and nature, was performed to characterize the evolving microstructure and the swelling. Comparison of 15Cr/15NiTi and 15Cr/25NiTi irradiated microstructure has lent insight into the effect of nickel content in the development of radiation damage caused by heavy ion irradiation. The results are quantified and discussed in this paper.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 475, July 2016, Pages 156-167
نویسندگان
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